ML19210E060
| ML19210E060 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 07/26/2019 |
| From: | Hironori Peterson Division Reactor Projects III |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| References | |
| IR 2019002 | |
| Download: ML19210E060 (19) | |
See also: IR 05000456/2019002
Text
July 26, 2019
Mr. Bryan C. Hanson
Senior VP, Exelon Generation Company, LLC
President and CNO, Exelon Nuclear
4300 Winfield Road
Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2INTEGRATED INSPECTION
REPORT 05000456/2019002 AND 05000457/2019002
Dear Mr. Hanson:
On June 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at
Braidwood Station, Units 1 and 2. On July 2, 2019, the NRC inspectors discussed the results of
this inspection with Ms. M. Marchionda, Site Vice President, and other members of your staff.
The results of this inspection are documented in the enclosed report.
The NRC inspectors did not identify any finding or violation of more than minor significance.
This letter, its enclosure, and your response (if any) will be made available for public inspection
and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document
Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for
Withholding.
Sincerely,
/RA/
Hironori Peterson, Chief
Branch 3
Division of Reactor Projects
Docket Nos. 05000456 and 05000457
License Nos. NPF-72 and NPF-77
Enclosure:
As stated
cc: Distribution via LISTSERV
x
SUNSI Review
x
Non-Sensitive
Sensitive
x
Publicly Available
Non-Publicly Available
OFFICE
RIII
RIII
NAME
NShah:bw
HPeterson
DATE
7/25/2019
7/26/2019
Enclosure
U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Numbers:
05000456 and 05000457
License Numbers:
Report Numbers:
05000456/2019002 and 05000457/2019002
Enterprise Identifier: I-2019-002-0059
Licensee:
Exelon Generation Company, LLC
Facility:
Braidwood Station, Units 1 and 2
Location:
Braceville, Illinois
Inspection Dates:
April 01, 2019 to June 30, 2019
Inspectors:
D. Kimble, Senior Resident Inspector
J. Robbins, Reactor Inspector
P. Smagacz, Resident Inspector
Approved By:
Hironori Peterson, Chief
Branch 3
Division of Reactor Projects
2
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees
performance by conducting an integrated inspection at Braidwood Station, Units 1 and 2 in
accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs
program for overseeing the safe operation of commercial nuclear power reactors. Refer to
https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
Type
Issue Number
Title
Report Section
Status
05000456,05000457/2
018012-01
Qualification of Conduit Seal
Removal for 2RY456 Limit
Switch
Closed
3
PLANT STATUS
Unit 1 began the inspection period operating at full power. With the exception of minor
reductions in power to support scheduled testing activities or small load changes requested by
the transmission system dispatcher, the unit remained operating at or near full power for the
entire inspection period.
Unit 2 began the inspection period operating at full power. With the exception of minor
reductions in power to support scheduled testing activities or small load changes requested by
the transmission system dispatcher, the unit remained operating at or near full power for the
entire inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in
effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with
their attached revision histories are located on the public website at http://www.nrc.gov/reading-
rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared
complete when the IP requirements most appropriate to the inspection activity were met
consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection
Program - Operations Phase. The inspectors performed plant status activities described in
IMC 2515 Appendix D, Plant Status and conducted routine reviews using IP 71152, Problem
Identification and Resolution. The inspectors reviewed selected procedures and records,
observed activities, and interviewed personnel to assess licensee performance and compliance
with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Summer Readiness Sample (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated summer readiness of offsite and alternate alternating
current (AC) power systems during the week ending June 22, 2019
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated system configurations during partial alignment verifications of the
following systems/trains:
(1)
1B Emergency Diesel Generator (EDG) with 1A EDG out of service for maintenance
during the week ending April 6, 2019
(2)
1A Containment Spray (CS) with 1B CS out of service for planned maintenance
during the week ending June 22, 2019
4
71111.05Q - Fire Protection
Quarterly Inspection (IP Section 03.01) (4 Samples)
The inspectors evaluated fire protection program implementation in the following selected
areas:
(1)
Fuel Handling Building, Fire Zone 12.1-0 during the week ending April 6, 2019
(2)
2A Residual Heat Removal (RH) Pump Room, Fire Zone 11.2A-2 during the week
ending April 27, 2019
(3)
Unit 1 Containment Pipe Penetration Area, Fire Zone 11.3-1 during the week ending
April 27, 2019
(4)
2A EDG Room, Fire Zone 18.2-2 during the week ending June 22, 2019
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 02.02a.) (1 Sample)
The inspectors evaluated internal flooding mitigation vulnerability and protection for the
following plant area:
(1)
Unit 2 'B' Essential Service Water (SX) Pump Room, Auxiliary Building Elevation 330'
during the weeks ending May 18 through June 1, 2019
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)
(1 Sample)
(1)
The inspectors conducted an evaluation of licensed operator performance in the
Control Room during various observations of on-watch Operations shift crews during
the weeks ending April 27 through June 29, 2019
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
(1)
The inspectors observed and evaluated a graded simulator scenario for a crew of
licensed operators on June 25, 2019
71111.12 - Maintenance Effectiveness
Quality Control (IP Section 02.02) (1 Sample)
The inspectors evaluated the licensee's maintenance and quality control activities
associated with the following equipment performance issue:
(1)
The failure of control power fuses for the 2A EDG as documented in Issue Report (IR)
4252176 during the weeks ending June 8 through June 29, 2019
5
Routine Maintenance Effectiveness Inspection (IP Section 02.01) (2 Samples)
The inspectors evaluated the effectiveness of routine maintenance activities associated with
the following equipment and/or safety significant functions:
(1)
A 1B Auxiliary Feedwater (AF) Pump performance issue associated with diesel fuel
oil seepage into the crankcase oil system as documented in IR 4238259 during the
weeks ending April 20 through June 29, 2019
(2)
An issue with the cubicle cooler fan motor bearing service life and run times for the
chemical and volume control pump cubicle coolers as documented in IRs 4244994,
4244974, and 4244975 during the weeks ending May 4 through June 29, 2019
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensee's assessment of risk associated with the following
planned and emergent work activities:
(1)
Planned 2-year maintenance on the 1A EDG as document in Work Order (WO)
4692594 during the week ending April 6, 2019
(2)
Emergent maintenance on the 1B AF Pump as documented in WO 4908688 during
the week ending April 13, 2019
(3)
Starting battery capacity maintenance and testing for the 2B AF Pump as
documented in WO 1836579 during the weeks ending April 20 through April 27, 2019
(4)
Unit 1 System Auxiliary Transformer (SAT) 142-1 maintenance inspections as
documented in WO 1945815 during the week ending May 11, 2019
(5)
Ground isolation activities on direct current (DC) Bus 111 as documented in WO 4920701 during the weeks ending May 18 through June 29, 2019
(6)
Emergent maintenance activities surrounding the failure of DC control power fuses for
the 2A EDG as documented in IR 4252176 during the week ending June 1, 2019
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 02.02) (6 Samples)
The inspectors performed evaluations of the following issues with respect to equipment
operability and/or functionality:
(1)
The licensee's decision to isolate primary water to the 1C Reactor Coolant Pump
(RCP) seal package standpipe as documented in IR 4224618 during the weeks
ending April 20 through April 27, 2019
(2)
Evaluation of excessive run time hours for the bearings on the 1B CV Cubicle Cooler
fan motor as documented in IR 4244994 during the weeks ending May 4 through
June 29, 2019
(3)
Evaluation of the minimum bus voltages for the Unit 1 SAT outage window as
documented in IR 4247579 during the week ending May 11, 2019
(4)
Evaluation of intermittent grounds on DC Bus 111 as documented in IR 4248185
during the weeks ending May 18, 2019 through June 29, 2019
(5)
Evaluation of degraded conditions for the valve 2AF005G manual loader (2HK-
AF036B) as documented in IR 4249077 during the week ending May 18, 2019
6
(6)
Evaluation of degraded performance associated with valve 2SX124A as documented
in IR 4253330 during the weeks ending June 8 through June 15, 2019
71111.19 - Post-Maintenance Testing
Post Maintenance Test Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the adequacy of the following post maintenance testing activities:
(1)
Functional and operational testing for 1B SX Pump following planned oil cooler
maintenance during the weeks ending May 18 through May 25, 2019
(2)
Functional and operational testing for check valve 2CC070B following disassembly
and inspection as documented in WO 1939834 during the weeks ending May 18
through May 25, 2019
(3)
Functional testing following investigation and repair of a high temperature connection
associated with 1AP27E, Division 1, during the week ending May 25, 2019
(4)
Functional testing following repairs on the cubicle cooler flow indicator sensing line for
the 1B CS pump during the week ending June 22, 2019
71111.21N - Design Bases Assurance Inspection (Programs)
The inspectors conducted the following activities:
Select Sample Components to Review - Risk Significant/Low Design (Inside/Outside
Containment) (IP Section 02.01) (1 Partial)
(1)
(Partial)
The inspectors reviewed actions to close Unresolved Item
05000456,05000457/2018012-01; "Qualification of Conduit Seal Removal for 2RY456
Limit Switch." These reviews by the inspectors did not constitute a separate stand-
alone inspection sample. Rather, they were an integral part of the original inspection
sample for this previously documented item.
71111.22 - Surveillance Testing
The inspectors evaluated the performance and conduct of the following surveillance testing
activities:
Surveillance Tests (other) (IP Section 03.01) (3 Samples)
(1)
2BwOSR 3.8.1.2-1: 2A Diesel Generator Semiannual Operability Surveillance - Timed
Fast Start during the week ending April 13, 2019
(2)
1BwOS MS-Q1: Unit 1 Main Condenser Steam Dump Operability Surveillance -
Timed Fast Opening during the week ending April 13, 2019
(3)
2BwOSR5.5.8.SI-10B: Group A Inservice Test (IST) Requirements for 2B Safety
Injection Pump during the week ending June 22, 2019
7
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification
The inspectors conducted a verification of the performance indicators listed below through a
sample of the licensee's submitted data:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (2 Samples)
(1)
Unit 1 (April 1, 2018, through March 31, 2019)
(2)
Unit 2 (April 1, 2018, through March 31, 2019)
MS06: Emergency AC Power Systems (IP Section 02.05) (2 Samples)
(1)
Unit 1 (April 1, 2018, through March 31, 2019)
(2)
Unit 2 (April 1, 2018, through March 31, 2019)
MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)
(1)
Unit 1 (April 1, 2018, through March 31, 2019)
(2)
Unit 2 (April 1, 2018, through March 31, 2019)
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
(1)
The inspectors reviewed the licensees corrective action program for potential
adverse trends involving multiple issues with the loose parts monitoring systems on
both units that might be indicative of a more significant safety issue during the weeks
ending May 3, 2019, through June 29, 2019.
INSPECTION RESULTS
Observation: Loose Parts Monitoring System Reliability
The inspectors performed a review of plant issues, particularly those entered into the
licensees CAP, associated with issues and failures of the loose parts monitoring systems on
both units. The loose parts monitoring system is described in Section 4.4.6.4 of the stations
Updated Final Safety Analysis Report (UFSAR) as a system that detects and alarms upon
sensing unusual noises that might indicate a metallic loose part within the reactor coolant
system. Operability requirements for the system in operational Modes 1 and 2 are set forth in
Section 3.3.d of the stations Technical Requirements Manual (TRM).
During their review, the inspectors noted that there have been several loose parts monitoring
system failures during the current operating cycles on both units. Currently, each unit has
three (of a total of twelve available) loose parts monitoring system channels in a degraded
and unavailable status, and due to accessibility issues with the equipment locations in
containment each degraded channel will remain unavailable for the remainder of the units
operating cycle. Given the systems overall significance, as indicated by its UFSAR and TRM
descriptions and requirements, additional review of system maintenance practices may be
warranted.
8
Additionally, during the course of the most recent inspection period, the inspectors noted that
a spurious Unit 1 loose parts monitoring system alarm was frequently being received at the
same time each morning on most days of the week over a several week period. Following
discussions with licensee management regarding the vulnerabilities associated with spurious
alarms causing the operating crews to become desensitized, this particular loose parts
monitoring system problem was traced to a computer coding issue within the systems
software and eliminated.
Unresolved Item
(Closed)
Qualification of Conduit Seal Removal for 2RY456 Limit
Switch
05000456,05000457/2018012-01
Description: The inspectors identified an unresolved Item concerning the removal of the
conduit seal of a NAMCO EA180 limit switch for the 2RY456 Pressurizer Power Operated
Relief Valve (PORV). Position indication of PORVs is a requirement outlined in NUREG-
0737, Clarification of TMI Action Plan Requirements, Enclosure 1, Post-TMI Requirements
for Operating Reactors, Item II.D.3, Valve Position Indication. These requirements were
incorporated prior to license issuance and are part of Braidwoods current licensing basis.
These switches are located in containment and could be exposed to a high temperature
steam environment during an accident. These switches were originally qualified for this
environment by Westinghouse. As documented in the Regulatory Guide 1.89 discussion in
UFSAR, Appendix A, (Page A1.89-1), For Westinghouse Nuclear Steam System Supplier
Class lE equipment, Westinghouse has met the requirements of IEEE-323-1974, IEEE
Standard for Qualifying Class lE Equipment for Nuclear Power Generating Stations including
the Nuclear Power Engineering Committee (NPEC) Position Statement of July 24, 1975, and
Regulatory Guide 1.89, Revision 0, by providing an appropriate combination of the following:
type testing, operating experience, qualification by analysis, and on-going qualification. This
commitment has been satisfied by NRC review and approval of Westinghouse Topical Report
Subsequently, the licensee performed an analysis that supported the removal of seals
associated with the conduit attachment to the limit switch without affecting its environmental
qualification. The inspectors were concerned that the subsequent analysis did not align with
detailed guidance located within IEEE-323-1974.
Initially, the inspectors viewed this lack of alignment as a potential performance deficiency.
After discussions with NRR technical staff and legal staff, the inspectors determined that no
performance deficiency existed. The basis for this conclusion was that 10 CFR 50.49,
Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power
Plants, does not currently invoke any specific standard. The information contained within the
licensee's UFSAR, when viewed as a historical reference, includes information about IEEE- 323-1974 because this information describes how equipment was originally qualified.
However, the requirements pertaining to IEEE-323-1974 were sunset upon the issuance of
the Final Rule, 50.49 (see Federal Register (FR), 48 FR 2733, Jan. 21, 1983, as amended at
49 FR 45576). As a result, no performance deficiency was identified.
Corrective Action Reference(s): AR 4120790 - NRC Question on Environment Qualification
Binder Evaluation of Limit Switches
9
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On July 2, 2019, the inspectors presented the integrated inspection results to
Ms. M. Marchionda, Site Vice President, and other members of the licensee staff.
On July 10, 2019, the inspectors presented the closure of Unresolved Item 2018012-01
to Mr. S. MacArtney, General Design Engineering Manager, and other members of the
licensee staff.
10
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
0BwOA ENV-1
Adverse Weather Conditions Unit 0
124
General Area Checks and Operator Field Rounds
16
OP-AA-108-107-
1001
Station Response to Grid Capacity Conditions
7
OP-AA-108-111-
1001
Sever Weather and Natural Disaster Guidelines
18
OP-BR-102-102-
1001
Augmented Operator Field Rounds
3
Seasonal Readiness
21
BwOP CS-E1
Electrical Lineup - Unit 1 Containment Spray system
Electrical Lineup
4
BwOP CS-M1
Operating Mechanical Lineup Unit 1
12
BwOP DG-E2
Electrical Lineup - Unit 1, 1B Diesel Generator
6
BwOP DG-M2
Operating Mechanical Lineup Unit 1, 1B Diesel Generator
17
Fire Plans
No. 104; Fire
Zone 11.2A-2
Auxiliary Building 364' Elevation RHR Pump 2A Room
1
No. 114; Fire
Zone 11.3-1
Auxiliary Building 364' Elevation Unit 1 Containment Pipe
Penetration Area
1
No. 104; Fire
Zone 11.2A-2
Auxiliary Building 364' Elevation Residual Heat Removal
Pump 2A Room
1
No. 114; Fire
Zone 11/3-1
Auxiliary Building 364' Elevation Unit 1 Containment Pipe
Penetration Area
1
No. 178; Fire
Zone 12.1-0
Fuel Handling Building 401' Elevation
1
No. 179; Fire
Zone 12.1-0
Fuel Handling Building 426' Elevation
1
No. 200; Fire
Zone 18.2-2
Auxiliary Building 401' Elevation Diesel Generator 2A &
Switchgear Room Air Shaft
0
Procedures
BwAP 1110-1
Fire Protection Program System Requirements
42
BwAP 1110-3
Plant Barrier Impairment program
38
BwOP PBI-1
Plant Barrier Control program
12
Plant Barrier Control Program
12
11
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
High Risk Fire Area Identification
4
ER-BR-600-1069
Site List of High Risk Fire Areas - Braidwood Unit 1 and Unit
2
0
Fire Prevention for Hot Work
16
Fire Protection System Impairment Control
0
Control of Transient Combustible Material
23
0BwOA PRI-8
Auxiliary Building Flooding Unit 0
9
BwAP 1110-3
Plant Barrier Impairment Program
38
BwOP PBI-1
Plant Barrier Impairment Program Pre-Evaluated Barrier
Matrix
3
Plant Barrier Control Program
12
Risk Management
7
OP-11-101-113-
1006
4.0 Crew Critique Guidelines
10
OP-AA-101-111-
1001
Operations Standards and Expectations
22
Operator Fundamentals
13
Watch Standing Practices
18
OP-AA-103-102-
1001
Strategies for Successful Transient Mitigation
2
Operation of Plant Equipment
1
Communications
4
OP-AA-108-107-
1002
Interface Procedure Between BGE/COMED/PECO and
Exelon Generation (Nuclear/Power) for Transmission
Operations
12
Operating Narrative Logs and Records
15
Reactivity Management
13
Systematic Approach to Training Process Description
5
Operator Training Programs
18
Conduct of Simulator Training and Evaluation
9
Examination Security and Administration
17
Simulator Management
9
TQ-BR-201-0113
Braidwood Training Department Simulator Examination
22
12
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Security Actions
Corrective Action
Documents
0881124
Long Range Planning for 1VA06CD Motor Refurbishment
02/16/2009
4238259
1AF01PB Crankcase Oil Analysis Degrading Trend
04/10/2019
4244974
1VA06SA Vibration Reading Results
04/30/2019
4244975
2VA06SA Vibration Reading Results
04/302019
4244994
1VA06CD Exceeds Run Time Threshold for Motor Bearings
04/30/2019
Procedures
Maintenance Rule Functions - Safety Significant
Classification
3
Maintenance Rule Implementation per NEI 18-10
0
Maintenance Rule 18-10 - Scoping
0
Maintenance Rule 18-10 - Performance Monitoring and
Dispositioning Between (a)(1) and (a)(2)
1
Calculations
BRW-97-0340-E
Battery Duty Cycle and Sizing for the Braidwood Diesel
Driven Auxiliary Feedwater Pumps
3
Corrective Action
Documents
2667064
Lessons Learned - Unit 1 System Auxiliary Transformer
(SAT) Outage Temporary State Estimator Alarm Setpoint
05/09/2016
4235979
Coating Repairs Needed for the 1DG01KA-X2 Lower
Stationary Head
04/03/2019
4235981
Coating Repairs Needed for the 1DG01KA-X2 Lower Pact
End Channel Head
04/03/2019
4235983
Coating Repairs Needed for the 1DG01KA-X1 Upper Pact
End Channel Head
04/03/2019
4235987
Debris Found Inside Stationary Head and Tubesheet
1DG01KA-X2
04/03/2019
4235988
Degradation Found During Inspection of 1DG01KA-X1
Upper Stationary Head
04/03/2019
4236145
Significant Amount of Oil in Air Sensing Line
04/04/2019
4236908
1A Diesel Generator South Fuel Rack Positioner Cable
Broke
04/06/2019
4236938
1A Diesel Generator Butterfly Valve Sticking
04/06/2019
4238259
1AF01PB Crankcase Oil Analysis Degrading Trend
04/10/2019
4240057
Battery Charger Lugs are Distorted on 2AF01EB-A Battery
04/16/2019
4247173
ACB 1441 Would Not Close Following SAT Restoration
05/02/2019
13
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
4247555
Ground Connections Corroded
05/08/2019
4247567
05/08/2019
4247579
Braidwood SAT Outage Restoration Delays
05/08/2019
4248106
SAT 142-1 Received Unsatisfactory Doble Test on X3
05/10/2019
4248185
Direct Current Bus 111 Ground
05/11/2019
Engineering
Evaluations
620474
Evaluation of Single SAT Operation on Unit 1 for 2019
0
Procedures
1BwOSR 3.8.1.1
Unit 1 Offsite AC Power Availability Surveillance
5
2BwHS 384-6
24 Volt ESF Auxiliary Feed Diesel Battery BT2 and BT2
Performance Test
0
2BwHSR 3.7.5-
BA
2B Diesel Auxiliary Feed Pump Battery Bank B Battery A
(2AF01EB-A) Capacity Test
3
2BwOS DC-Q4
24V DC Auxiliary Feed Pump 2B Battery Bank A and B
Quarterly Surveillance
6
BwHP 4006-023
Bus Disconnect Link Relocation on 6900 V SAT Buses
8
BwHP 4006-059
Operation of the Biddle/AVO Ground Fault Tracer
3
BwHP 4006-066
DC Bus Ground Location Using the Multi-Amp Battery
Ground-Fault Locator
1
BwHP 4006-074
Bus Disconnect Link Relocation on 4160 V SAT Buses
4
BwHS 4002-084
System Auxiliary Transformer Preventative Maintenance
Inspection
15
BwMP 3100-022
Diesel Generator 2 Year Inspection
38
BwMP 3200-014
Auxiliary Feedwater Pump Diesel Drive Unit Inspection and
Maintenance
22
BwOP AP-15
Isolating System Auxiliary Transformer (SAT) 142-1 with Unit
1 Unit Auxiliary Transformer (UAT) Energized
27
BwOP AP-20
Restoring System Auxiliary Transformer (SAT 142-2) with
Unit 1 UAT Energized
21
BwOP AP-54
With SAT 142-1 Isolated, Isolate SAT 142-2 and Restore
SAT 142-1 with Unit 1 UAT Energized
11
BwOP DC-E2
Electrical Lineup - Unit 1 Operating - 125 Vdc Division 11
9
ASME Section XI Repair/Replacement Program
16
ER-AA-335-015-
VT-2 Visual Examination in Accordance with ASME 2013
0
14
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2013
On-Line Risk Management
11
MA-AA-716-230-
1004
Lubricant Sampling Guideline
5
MA-BR-EM-4-
09070
Diesel Generator Electrical Inspection
16
Protected Equipment Program
5
On-Line Risk Management and Assessment
2
Integrated Risk Management
25
Work Orders
1836579
24 Volt Auxiliary Feed Battery Bank Capacity Test
(2AF01EB)
04/15/2019
1945815
1AP02E: Preventative Maintenance Inspection of SAT 142-1
05/07/2019
4692594
1DG01KA: 24 Month Inspection of the Diesel Generator
04/01/2019
4693700
1DG01EA: Diesel Generator Exciter Inspection (1A EDG)
04/01/2019
4908688
1AF01PB Crank Case Oil and Filter Change
04/12/2019
4920701
DC Bus 111 Ground
05/13/2019
Corrective Action
Documents
2667064
Lessons Learned - Unit 1 SAT Outage Temporary State
Estimator Alarm Setpoint
09/09/2016
4194175
1PL01J Alarms Generate DC Bus 111 Ground Alarm
11/12/2018
4209879
DC Bus 111 Ground Coming in with 1PL01J Panel Check
01/10/2019
4223051
1RF008 Flowrate Trend Anomaly
02/24/2019
4224618
1CV179 Cycling Excessively
02/28/2019
4228652
1RF009 Elevated Reading
03/12/2019
4229675
Unit 1 Floor Drain Sump Channel A Failed - PC002
03/15/2019
4244974
1VA06SA Vibration Reading Results
04/30/2019
4244975
2VA06SA Vibration Reading Results
04/30/2019
4244994
1VA06CD Exceeds Run Time Threshold for Motor Bearings
04/30/2019
4247579
Braidwood SAT Outage Restoration Delays
05/08/2019
4248185
DC Bus 111 Ground
05/22/2019
4249077
2HK-AF036B: Manual Loader for 2AF005G Failed - WO 1893938
05/15/2019
4253330
2SX124A is Very Difficult to Operate
05/31/2019
4254702
Erratic 2A CV Pump Cubicle Cooler SX Flow Rate
06/05/2019
15
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Engineering
Changes
Performance of Cubicle Coolers 1VA06SA and 2VA06SA
with One or Two Fans in Operation
0
Procedures
1BwOS DC-1a
AAR-125 Vdc ESF Bus Ground
8
BwOL 3.8.4
LCOAR
DC Sources - Operating Technical Specification LCO 3.8.4
8
BwOP DC-23-111 125 Vdc Bus 111/113 Ground Detection
4
Administrative Requirements for Inservice Testing
13
Risk Management Documentation
14
Risk Assessments of Missed or Deficient Surveillances
7
OP-AA-106-101-
1006
Operational Decision Making Process
21
Adverse Condition Monitoring and Contingency Planning
13
Operability Determinations (CM-1)
21
Corrective Action
Documents
4257536
2SI8804B Mechanical and Grease Inspection
06/17/2019
4257539
2SI8912B has Inactive Packing Leak
06/17/2019
Procedures
2BwOSR
5.5.8.SI-10B
Group A IST Requirements for 2B Safety Injection Pump
(2SI01PB)
10
BwOP SX-1
Essential Service Water Pump Startup
23
BwOP SX-7
Swapping Essential Service Water Pumps
27
Section XI Pressure Testing
16
ER-AA-335-015-
2013
VT-2 Visual Examination in Accordance with ASME 2013
0
Work Orders
1938834
Disassemble and Inspect 2CC070B
05/14/2019
1939833
2CC9520B Disassemble and Inspect
05/14/2019
1955970
EQ Motor Containment Spray Pump 1B
06/18/2019
4615529
1SX01AB Cooler Inspection and Cleaning
05/16/2019
4838800
Flow Indicator Containment Spray Pump Room Cooler 1B
Outlet
06/18/2019
4889939
ESF Switchgear Room Division 12 Ventilation System Vent
Fan Motor
05/22/2019
4906923
IST for 1CS003B/11B - ASME Surveillance Requirements
for 1CS01PB & Check Valves
06/18/2019
Corrective Action
4238267
Valve Handle Not Moving Valve Stem Properly
04/10/2019
16
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
4238279
Fuel Oil Leak From Left Bank Fuel Rail
04/10/2019
4238284
2PI-DG030A Turbo Air Inlet Pressure Indication is Suspect
04/10/2019
4238291
2A EDG Fuel Rack Trip Level Pushbutton Fell off During
EDG Run
04/10/2019
Procedures
1BwOS MS-Q1
Main Steam Dump Valve Stroke Surveillance
11
2BwOSR 3.8.1.2-
1
2A Diesel Generator Operability Surveillance
47
BwOP DG-1
Diesel Generator Alignment to Standby Condition
30
BwOP DG-11
Diesel Generator Startup and Operation
51
BwOP DG-12
Diesel Generator Shutdown
30
Work Orders
4836509
2A Diesel Generator Operability Semi-Annual Surveillance
04/10/2019
4876995
Unit 1 Steam Dump Valve Quarterly Surveillance (Tave
Mode and Above P-8)
04/11/2019
4898251
2A Diesel Generator Operability Monthly Surveillance
04/10/2019
71151
Corrective Action
Documents
4236155
Unexpected Unit 2 Loose Parts Alarm
04/04/2019
Miscellaneous
NRC Performance Indicator Data; Mitigating Systems -
Safety System Functional Failures
04/01/2018 -
03/31/2019
NRC Performance Indicator Data; Mitigating Systems -
Mitigating System Performance Index for Emergency
Alternating Current Power
04/01/2018 -
03/31/2019
NRC Performance Indicator Data; Mitigating Systems -
Mitigating System Performance Index for High Pressure
Injection
04/01/2018 -
03/31/2019
Procedures
Collecting and Reporting of NRC Performance Indicator
Data
15
Monthly Data Elements for NRC Safety System Functional
Failures
7
Mitigating System Performance Index date Acquisition and
Reporting
6
Corrective Action
Documents
4209142
Unit 2 Loose Parts Alarm
01/08/2019
4210587
Unexpected Alarm, Loose Parts
01/14/2019
4211151
Trend in Loose Parts Monitoring Issues
07/15/2019
4212438
Unexpected Annunciator 2-13-E9, Loose Parts Monitoring
01/20/2019
17
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
System Trouble
4213338
Received Unexpected Annunciator 2-13-E9, Loose Parts
01/23/2019
4216074
Unit 2 Loose Parts Alarm
01/31/2019
4217622
Unit 1 Loose Parts Alarm
02/05/2019
4219216
Unexpected Annunciator: 2-13-E9
02/12/2019
4227893
Unit 2 Loose Parts Monitoring System Impact Noise Alarm
Channel 4
03/08/2019
4228922
Loose Parts Alarm - Channel 1, 3, 14 - No Abnormal Noises
03/13/2019
4232957
Metallic Noise Unit 1 Loose Parts Monitoring System at 1C
SC Lower Narrow Range Level Tap
03/25/2019
4233318
Reactor Vessel Head Loose Parts Monitoring System Alarm
Disabled 2VE-LM002
03/26/2019
4236155
Unexpected Unit 2 Loose Parts Alarm
04/04/2019
4236932
Unexpected Annunciator: 2-13-EP
04/06/2019
4237724
Unexpected Unit 1 Loose Parts Alarm
04/09/2019
4242027
Unexpected Unit 2 Loose Parts Alarm
04/22/2019
4245172
Unexpected Annunciator 1-13-E9
05/01/2019
4248952
Need Work Request to Troubleshoot Unit 1 Loose Parts
Monitoring System Channel 1
05/14/2019
4250626
Re-Evaluate Loose Parts Monitoring System Oversight
05/21/2019
Miscellaneous
Maintenance Rule 18-10 - Failure Definitions
0
Procedures
BwOP LM-10
Loose Parts Monitoring System Operation and Alarm
Response
4
BwOP LM-10A1
Loose Parts Monitoring System Alignment
3
Quality Assurance Topical Report (QATR)
7
Protected Equipment Program
5
Pre-Fire Plan Manual
4
PI-AA-=125-1001
Root Cause Analysis Manual
3
Issue Identification and Screening Process
8
Corrective Action Program (CAP) Procedure
6
Corrective Action Program Evaluation Manual
4